openmc.DelayedGroupFilter

class openmc.DelayedGroupFilter(bins, filter_id=None)[source]

Bins fission events based on the produced neutron precursor groups.

Parameters:

  • bins (iterable of int) – The delayed neutron precursor groups. For example, ENDF/B-VII.1 uses 6 precursor groups so a tally with all groups will have bins = [1, 2, 3, 4, 5, 6].

  • filter_id (int) – Unique identifier for the filter

Variables:

  • bins (iterable of int) – The delayed neutron precursor groups. For example, ENDF/B-VII.1 uses 6 precursor groups so a tally with all groups will have bins = [1, 2, 3, 4, 5, 6].

  • id (int) – Unique identifier for the filter

  • num_bins (Integral) – The number of filter bins

check_bins(bins)[source]

Make sure given bins are valid for this filter.

Raises: